Heat Transfer Essay

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Heat transfer from high temperature heated surfaces finds considerable application in engineering. Because of its large number of applications in industries, considerable efforts have been made by researchers to investigate various aspects of the heat transfer and its fundamental principles involved. Fluid flow problems involving heat transfer viz. in presence of convention and radiation represents an idealization of many meaningful problems in engineering practice. Due to the presence of higher level of temperature required in many system like boiler, nuclear reactor; the effect of radiation heat transfer increases. So, there becomes a need of including radiative effect of the participating medium and also their boundary conditions. Keeping this in mind, an attempt was made to investigate the heat transfer in the Indian Pressurized Heavy Water Reactor (IPHWR) during Loss of Coolant Accident (LOCA) with low steam flow. This study will help in estimating the safe working limits for the heat dissipation in the reactor.
A nuclear power plant is a thermal power station in which the heat source is a nuclear reactor. That nuclear power plant is similar to that of conventional power plant where the boiler is replaced by a nuclear reactor. As is typical in all conventional thermal power stations the heat is used to generate steam which drives a steam turbine connected to a generator which produces electricity. In a typical nuclear reactor the reactor core acts as heat exchanger, as the heat is generated by nuclear reaction, the generated heat is transferred to the primary cooling medium which is heavy water (D2O). Outside the reactor core, the primary coolant exchanges heat with the secondary fluid (water) to generate steam to be used in...

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...appen at a time (Gopal et al., 2010).
India’s current Nuclear Power Plant program is based on long term objectives and availability of resources as well as infrastructure for their self-dependence and energy security for long term and efficient working (Bajaj et al., 2006). An in-depth study is always required to be done to avoid any possibilities of accidents related to nuclear hazard. Though, the occurrence of accidents has a very low probability, but still they do have consequences on nuclear fuel degradation. Hence there is a need for the safety analysis of IPHWR in case of LOCA.
Numerical investigation has been carried out to study about the temperature distribution of the reactor channel under LOCA with fuel rods deformed and undeformed under high temperature heat transfer. The numerical work of simulation would be done in commercial CFD software ANSYS 14.0.

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